Modeling of fission gas effects observed in TREAT loss-of-flow test R8 using SAS3D. [LMFBR]
The TREAT loss-of-flow test R8 has been analyzed using a modified version of the SAS3D accident analysis code in order to establish experimental verification of SAS3D modeling changes introduced to assess the effects of fission gas release from the upper gas plenum on coolant voiding dynamics and clad motion prior to the onset of fuel motion in whole core accident studies. The specific motivation for the analysis was the necessity of investigating the potential for fuel compaction by the fission gas stored in the gas plena at the upper end of the fuel pins in the Clinch River Breeder Reactor Project (CRBRP). These investigations were required to support licensing activities underway just prior to the demise of the project. In test R8, an unirradiated, seven-pin fuel bundle was subjected to a simulated Fast Flux Test Facility flow coastdown. The power was held constant at its nominal value.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5913518
- Report Number(s):
- CONF-850410-29; ON: DE85004822
- Resource Relation:
- Conference: ANS/ENS fast reactor safety meeting, Knoxville, TN, USA, 21 Apr 1985
- Country of Publication:
- United States
- Language:
- English
Similar Records
Interim Report on TREAT Test R8, a Seven-Pin Loss-of-Flow Test with Pressurized Pins -- Part 1
Interim Report on TREAT Test R8, a Seven-Pin Loss-of-Flow Test with Pressurized Pins -- Part 2
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ELEMENT FAILURE
FISSION PRODUCT RELEASE
LMFBR TYPE REACTORS
LOSS OF FLOW
COMPUTER CALCULATIONS
REACTOR SAFETY
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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